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. NUCLEAR POWER PLANT DESIGN CONCEPTS FOR SABOTAGE PROTECTION Volume I 1. INTRODUCTION ,. , The objectives of this program are to estimate the potential value of various configurations of plant design and damage control measures in providing protection againgt sabotage at commercial light water reactor (LWR) power plants and to establish the impact of such measures on facility costs, operations, and safety. The program emphasizes new designs and future construction: therefore, design changes that might be retrofitted to existing plants or to plants under construction are not addressed here. Phase I of this program was structured to identify a range of measures, document them in a consistent fashion, provide. a preliminary evaluation, and select the most promising ones for further consideration in Phase 11. Phase 11 wan thus intended to provide a limited number of detailed designs with a more complete evaluation of values and impacts. This report details Phase I of the program, summarizes the conclusions reached to date, a and makes some recommendations for additional study, including sub- stantial revision and redirection of Phase 11. b Background This program to investigate design concepts for sabotage protection evolved fran the reconmendations of earlier studies 1,2,3,4 and from views expressed by representatives of the Nuclear Regulatory Canmission (NRC) Office of Nuclear Reactor Regulation, the Advisory Committee on Reactor ~ afe~uards,~ and the nuclear power industry. 6
: A sahotaqe t-hreat nay arise from a determined violent external assault, att.ack by stealth, or deceptive actions, of several persons: or from the activities of an insider who could be an erployec in any position. On this hasis, the previous studies identifie,! three catr- gories of measures which provide sahotaqe protection: (1 ) physical protect ion, ( 2) plant desiqn, and (3) (l;trn,rqe control . C~~rrent Depart- ment of Enerqy (DOE) and NRC fiafequarrls research eryhasizr.s systcr development and evaluation of the effectiveness of physical protection measures or systems. The proqram described in ellis report was designed to ccmplement the onqoinq DoE/NHc research by investiqating the t wo remaininq categories of .safequards measnres for I.WR power plants: plant desiqn and danaqe control. In the context of this program, plant design (or plant design measures) is understood to encom- pass those measures that can be employed in the design and fabrication of operational systems or in plant layout to increase the difficulty of sabotage (decrease component or system vulnerability)* or to hetrer accommodate physical protection or damaqe control measures (decrease plant vulnerability). Similarly, damaqe control encompasses those actions which can he taken within a short time after radiological sabotage to prevent or reduce the release of radioactive materials. Public Risk Rationale for Study The question of public risk from a wide range of eneroy-producinq activities is receiving increasing attention in today's society. It would perhaps he satisfyinq if all such questions could be addressed in a single, coherent study so that public decisionmakers could read- ily and straightforwardly evaluate the relative public rlsk of enerqy alternatives. However desirable, such a study unfortunately qoes far beyond the intent and scope of this proqrarr. Therefore, in this ef- fort, only the public risk from potential malevolent acts aqainst a single energy producer, i.e., nuclear power plants, is considered. -t A glossary of definitions of terms (e.y., vulnerability) used in this study and report is given in Appendix A.
Page 1 and 2: Annette Vietti-Cook, Secretary U.S.
Page 3 and 4: No. (3) Comment aircraft impact, wi
Page 5 and 6: No. (5) Comment December 14, 2007 P
Page 7 and 8: NUCLEAR POWER PLANT DESIGN CONCEPTS
Page 9 and 10: ABSTRACT . Using a modern design fo
Page 11 and 12: CONTENTS (Continued) Traditional Co
Page 13 and 14: ILLUSTRATIONS (Continued ) Figure 7
Page 15 and 16: Table TABLES (Continued) 8-2 Probab
Page 17: RCS RHRS RPS RSS RTS RWST SAFE SIS
Page 21 and 22: I Public risk clue to sabotage is,'
Page 23 and 24: Somewhat contrary to the physical s
Page 25 and 26: I General Program Flow and Scope 2.
Page 27 and 28: Baseline Plant Characterizatlon The
Page 29 and 30: * Damage Control Options - In this
Page 31 and 32: Evaluation of Preliminary Reference
Page 33 and 34: :iabotaye . Vault '~'rcc for Plant
Page 36 and 37: Prom a fault tree, an equlvdlent ii
Page 38 and 39: 4. Reactor protrrt ion syster (PI'S
Page 41 and 42: loss-of-coolant accident (LoCA) rit
Page 43 and 44: mitigate or prevent damage to the c
Page 45 and 46: Vital - Area Analysis The primary e
Page 47 and 48: When the complement of the location
Page 49 and 50: . , 3 ..: 1. Hardening critical sys
Page 51 and 52: I Addition of Systems -- The final
Page 53 and 54: Table 4-1 Categorization of Design
Page 55 and 56: Although the attributes described a
Page 57 and 58: A summary of the initial findings o
Page 59 and 60: observation can be made for isolati
Page 61 and 62: Several options (i.4, 11.6, and 11.
Page 63 and 64: Table 4-5 Categorization of Design
Page 65 and 66: , . .,. . . - . . . . ~ Findings on
Page 67 and 68: For example, additional remote indi
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would be to use the plant fire prot
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with such events and because the co
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initial condition, the time availab
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' All reactor control rods are assu
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Option Function Table 5-3 Evaluatio
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the fifth option, which has only mi
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the problem, ( 3) assess the diffic
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other difficulties that were beginn
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Table 6-1 Cost Estimate Summary of
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of 4 to 13 minutes based upon data
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excavation, a base mat, and tank. T
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0 J @ a CONTAINMENT ELM;. PENETRATI
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RECIRC. O OVERHEAD CDNTAlMNT LCY-HE
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opq BORIC ACID STORAGE TANKS .
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.. . 2 (ft I . . .'._ . ,, . ., ' .
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were considered, but their inclusio
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Table 6-4 Cost ~stimates for. Equip
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modified plant (see Appendix G) and
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qp PRESSURIZER
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DHRS, startup of the diesel generat
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The compressor also supplies contro
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Table 6-6 Cost Estimates for Harden
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Table 6-8 Piping Connections to Rea
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I The normal letdown piping, being
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7. PHYSICAL PROTECTION SYSTEH The p
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Secure central alarm station, Locks
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I is doors between the turbine hall
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Figure 7-4. Locations of Locked and
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,,.' Table 7-1 Characteristics of E
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with the baseline plant, there is a
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KEY 'ENGINEERED SAFETY FEATURE WATE
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KEY 0 STAnDARD DOOR: CARD READER/AL
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KEY fl STANOAR0 DOOR: KEY Figure 7-
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Table 7-4 Characteristics of Interi
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2. Increase the number of individua
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last barrier to vital equipment is
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Vital Area mergmncy cwling piping/v
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are generally comparable with the b
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caution is appropriate. For example
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Table 8-3 Typical Permanent Staffin
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Plant Ares Control rom PYR containm
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. , access to both trains as part o
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CHARGE PUMP Figure 8-3. CHARGE PUMP
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Effectiveness of Hardened Decay Hea
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the future to examine impacts or co
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compartments are adjacent or access
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If total plant costs are assumed to
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event that manual [peration is nece
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!X torque limiters on selected letd
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9. CONCLUSIONS AND RECOMMENDATIONS
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APPENDIX A Glossary of Terms Used i
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system vulnerability) or to better
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APPENDIX B Public Riek Due to Sabot
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where The risk due to sequence j le
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of damage control or consequence mi
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4 3. Physically separate vital comp
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APPENDIX C The Design Study Technic
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Name Alan R. Kasper Tobias W. T. Bu
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'5. W. Hickman, "Systems Analysis,
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NUCLEAR POWER PLANT DESIGN CONCEPTS
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TAKING ADVANTAGE or NATURAL PROTECT
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4.11 SEI'AIU'PION OF SAFETY IICIATE
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. . . , ' . . . . . . , ., , , , .
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,.. . ,. Providing enhaxed protecti
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2 1 . 3 Desirable Attr~tutes of Can
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TABLE 1-1 (can't) 'The column head~
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. . ... . l I I. SYSTEM DES IG3 CHA
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CATECORlZATlOll OF DESICI~I ALT - ,
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GENE RAL 3. DESCRIPTIOtG AND CISCUS
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of war. The ring tunnel containment
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3.3 MARDENED CONTAINMENT BUILDING,
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. ' :, mcnt entry. These factors op
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3.4.5 Summary - - - of DSTSG - Inpu
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. . . , It was also pointed out dur
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3.6.5 Summary of DSTSG Input There
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. . . . . , , mcntator felt that co
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3.8.1 Disadvantages. If ,this conce
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systems and houzing them in separat
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. , in some G.S. ~lsnts. At San Cno
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well as location of the spent fuel
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3d3.2 -. Sources This concept h.3::
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There were no side benefits idcntif
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3.14.4 - Disadvantages t The main d
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3.15.3 Advantages .. . The sabotage
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3.16.2 ---- Sources Physically sepa
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Indqpcndencc is considered low for
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3.18.2 Advantages The counter-sabot
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Depending on the means of implement
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power jumper cables, etc., to facil
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epairs under satotace emergency con
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3.21.3 Advantages The alternate con
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The counter-sabotayc aspects of und
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3.22.4 Disadvantages > The disadvan
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3.23.4 . . Disadvantages This conce
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3.24.6 Discussion The discussion pr
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' There was no clear indication of
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Thc DSTSG considered inpacts for th
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3.27.6 Discussion This concept ellm
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The concept of a RHR system designe
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Appendix C contains a description o
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. System capacty is limited in time
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The DSTSS has raised questions on t
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controls and hardened enclosures, t
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. Summary Comparison of Ee$t Europe
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Applying Gernan Safety Philosophy a
Page 301 and 302:
4.16 ALTERXhl'E CONTROL ROOF! ARRAN
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. Design of Kr;Z' Lh'R Safety Syste
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. Standby and Esergency Power Suppl
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This Addcndun cuntai ns sununar ies
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I CATEGORY: 1.2 HARDENED CONTAINMEN
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CATEGORY: 1.4 HARDENED ENCLOSURE OF
Page 314 and 315:
CATEGORY: 1.6 HARDENED ULTIMATE HEA
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CATEGORY: 1.8 HARDENED ENCLOSURE FO
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CATEGORY: 11.2 SEPARATION OF PIPZNG
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CATEGORY: 11.4 SPENT FUEL STORED RE
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CATEGORY: 11.6 SEPARATE ROOMS OR AR
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CATEGORY: 11.8 ECCS COMPONENTS WITH
Page 326 and 327:
CATEGOPY : I I I. 1 ISOIAT ION OF L
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CATEGORY: 111.3 ALTERNATE CONTAINKE
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CATEGORY: 111.5 ADDITIOSAL PROTECTE
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CATEGORY: 111.7 TURBINE RUNBACK NUI
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PEASIUILI'fY STATE OF TIIE AIVI' PR
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CATEGORY: IV.l HARDENED CECAY HEAT
Page 338 and 339:
Systt:m st~ou~d rlnt bc rt,str ictc
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System Description Independent Safe
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. , 2. A sinqle system: : 3. A sing
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I period of 10 hours without operat
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the initial phase of shutdown cooli
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Actuation of the ISSS results in th
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prcsurizer relief valves. Gradually
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Some of these fluid lines arc pro-~
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. ~ ,. : " The turbine is driven by
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. . coolant pressure that can be ob
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Feedwater Storaye Tank Each feedwat
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ISSS A:mosphcr1c D G T ~ Val.io?, ?
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A conceptudl arrdngement 1s st,~wn
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systems would he employed in thc BW
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As long as the time for ISSS opcrat
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., ! 4 I 3 1 2 - . ! I,. ,.Y- .,.I'
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Potential Safcguar
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SECTION 3.5 Reactor Vessel Head Ven
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FIGURE 2-12 : 2-13 5,: . .. . 2-14
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P;IR Systems AC Power 1.7 Reactor C
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DESIGN CHANGE Table 1.1. AC Power S
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DESIGN CHANGE Increase battery capa
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I I Replace I I (1) Table 1.5. Gene
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Table 1.7. PWA AC Power Syst DESIGN
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I I I I Table 1.9. PWR Auxtttary Fe
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i Tahle 1.10. Emergency Core Coolin
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1.. DESIGN CHANGE Table 1.12.BWRRes
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DAMAGE CONTROL ACTIVITY Jrovide a s
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Figure 2-1. AC Power System Design
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2.2 SWITCHGEAR AN0 K CATEGORY I I1
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are discussed in mre detail in a la
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2.5 UICSEL ft4CINE REV:SED COOLING
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Figure 2-3. Diesel Cooling and Lubr
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2.6.5 Discussion An emergency diese
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equipnent. !%tor. controllers and d
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Table 2-1. Safety-Related DC Loads
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fnstrunrntation channel powered fro
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2.11.5 Oi scussion The concern over
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2.12.2 Source This concept was iden
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equipment during routine plant surv
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insider sabotage and the dlfflcul t
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2.16.3 Advantages The advantage of
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2.17.1 Concept Thls concept 1nvolve
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2.18 COFPONEKT COOLING MOOIFICATION
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to accomplish both functions with o
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2.19.4 . Disadvantages The lujor di
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VALVE C00113B WATER ISOLATION VALVE
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....,.. c., Frol Other Loads To Ult
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g u Outslde Alr / I Roof or Ida11 a
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, . accessibility to the diesel and
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. . .,,. . .. . .,. ,, ..* . . .. ,
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3.3.4 Disadvantages No disadvantage
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jI..'$ . $ 5 $!, .. . .:.;,: . ., I
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Vmt Path A Figure 3-1. Reactor Vess
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3.7.2 Source Thls concept was tdent
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Pressurl zer c + hxlllrry Elect. /
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3.9 INCREASED EMERGEtiCY FEEOWATER
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pmvfded. In the case of a narltiple
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3.11.3 Advantages The advantage of
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For operating plants which utilize
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3.14.5 Discussion As mentioned in S
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3.16.4 Dl sadvantages The disadvant
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utfll ttd f n the RHR suction 1 lne
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0 The heat exchanger shell provides
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of two tube bundles imacrsed in a l
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0 Provide an offsite reserve supply
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condtttons, is a straightforward ma
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REFERENCES '''power Plant Insulatto
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Introduction EVALUATION AND SUMMARY
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Table A-1 (Continued) Cdtryorlzntio
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. , 2.4 MULTIPLE UNIT V;lAL kC LRUS
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3.1 CLASS 1E AUXILIARY STEAM TCRBIN
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envirorments. with the presence of
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Table of Contents List of Tables Li
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Fiq n-1 Fig C2-1 Fig C2-2 Fig C2-3
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1.3 PURPOSE The purpose of this wor
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2.1 DA.NAGE CONTROL ACTIONS The dam
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ased on a variety of events (e.y..,
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2.2.4 Reactor Vessel Decay Neat Rem
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2.2.5 Spent Fuel Pool L I If sabota
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5. Keeping damage control storage l
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V., ,"". van lour
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COMMENTS : . This may add another s
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ENGINEERING CONCERNS: The proper NP
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COMMENTS : I . . . . Hydraulic Limi
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ITEM: EVALUATION NO. 5 (PWR) Manual
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EVALUATION NO. 7 ITEM: (BWR) Substi
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, ; . ,. . ITEM : FUNCTION : EVALUA
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EVALUATION N e ITEM: (BWR) Provide
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ITEM: FUNCTION : EVALUATION NO. 12
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EVALUATION NO. 13 ITEM: (BWR 6 PWR)
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COMMENTS : . Any condensate used mu
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COMMENTS : Regulatoey concerns abou
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ENGINEERING CONCERNS: Some componen
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EVALUATION NO. 18 ITEM: (PWR) Steam
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ENGINEERING CONCERNS: A desiqn effo
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ITEM : FUNCTION : EVALUATION NO. 21
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EVALUATION NO. 22 ITEM: (BWR & PWR)
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F-G 0 OPERATIONAL CONSIDERAT1:ONS :
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ITEM: EVALUATION NO. 25 (PWR & BWR)
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1 A 1: AVAllAR1.E TISE CASE SEI.ECT
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Case number: 2 Description: A charg
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Case number: 3 . . ~escription: The
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Case number: 5 Description: The res
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Case number: 6 Description: Loss of
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TO Calculate the heat required for
Page 561 and 562:
Page 563 and 564:
Results: Assuming the initial condi
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Case number: 10 Description: RHR pi
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Case number: 12 Description: Drain
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case Huther Table 8-22 AVAILAb1.E T
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Page 573 and 574:
The heat required for each p h~se i
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Page 577:
lr~ss-01 -cwlant yceater than charg
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APPENDIX B: INITIAL APPROACH TO DAM
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I i i i ~ClncheI :c .%r:a-;cw: ' w
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however, not all systems listed by
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Acquire Damage Assuming there are s
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6. Establishing the Limits of Trans
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TABLE 0-3: SABOTAGE TIME LINE RESUL
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Hllog in fuel ull inuck LC
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LC TIME MWIW ULSIW -ntsk:- l!*uf"l
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3 lnqlne starts or rrtanpcs Ea star
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2 Enqtce s:ops. wall nor car=/ load
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" ., . Initratfan 0 sabotaqa event
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0 enq-he starts or at:empts t3 Star
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SXBCTACE XODE: 5tar:l-q alr tank de
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inirration 0 Albms and indications
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SYSTS..: Relidudl Heat Ramova?. jys
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Initilz~on 0 Demand tar X. syeern.
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Iaitiacion 0 Demand :sr Afi4 yYtel.
Page 618 and 619:
34-i~2 min. Note: Riarnq stem '~alv
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SYSTZX: Auxa;;ar( Peedwe-er System
Page 622 and 623:
C~n=:?l Room Response u :ntar!al fo
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:2itlrtion 0 Sabocaqe event occurs.
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112-1147 min. IAsswrnq sp1ic:nq. no
Page 629 and 630:
Xiamo and :ndrcatrans 9-13 nm. Cont
Page 631:
SYSTPV: 48OV Class :E Electrical 3i
Page 634 and 635:
For each model (BWR and PWR), the f
Page 636 and 637:
FUNCTIONS - Primary Coolant Invento
Page 638 and 639:
Chemical and Volume Control System
Page 640 and 641:
electric power is interrupted, the
Page 642:
." ,.,- 4160 VAC (vital) 125 VDC TA
Page 645 and 646:
does not have an extensive power hi
Page 647 and 648:
TABLE C2-5 PAlN FEEDWATER SYSTEM i
Page 650 and 651:
ESW pumps are on standby with cooli
Page 653 and 654:
features (ESF) transformer. Table C
Page 655 and 656:
FIGURE C2-7 DC Electric Distributio
Page 657 and 658:
FIGURE CZ-8 Coinponent Coolli~g h'a
Page 659 and 660:
. ESW'S~S~~~. The ESW system could
Page 661 and 662:
C3. BOILING WATER REACTOR (BWR) APP
Page 663 and 664:
I - -1- -- .
Page 665 and 666:
via the main steam safety/relief va
Page 667 and 668:
250 VDC FUNCTIONS TABLE C3-3 HIGH P
Page 669 and 670:
125 VDC 4160 VAC (vital) Condensate
Page 671 and 672:
41 hU VAC 125 VIK' TABLE C3-5 CORE
Page 673 and 674:
I*.',. -.- taw Residual Iledt Remov
Page 675 and 676:
eactor vessel by manually dumping s
Page 677 and 678:
Service Water System
Page 679 and 680:
cooling on an individual basis. Suc
Page 681 and 682:
Emergency Service Water System FUNC
Page 683 and 684:
FIGURE C3-7 DC Electric Distributio
Page 685 and 686:
Therefore, onl: valves accessible f
Page 687 and 688:
, : %..- ~ DC 1. Reactor Water Leve
Page 689 and 690:
APPENDIX D: COMPUTER CALCULATIONS F
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69 F i yur c 1)- 1 : HEACI'OR MOIIE
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680.0 660.0 640.0 620.0 600.0 JBO.0
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- - - - - - - - - STATION BLACKOUT
Page 698 and 699:
TIHE (SECONDS) XI0 j - 7 PHESSUHI Z
Page 700 and 701:
. LMTAI: 050141 [ 2Zon.tt I -1. I .
Page 704:
'-. - - - . - - - -- . . . HEAT S i
Page 707 and 708:
APPENDIX E: INDUSTRY SUR'JEYS At th
Page 709 and 710:
2. In the cases of the oil refineri
Page 711 and 712:
Concept De~e~lopment and Cost Estim
Page 714 and 715:
- PAGE ' 4.5 Cost Estimates for Iso
Page 716 and 717:
!;cl~crn;~tic Arrangemcrnt of ESF h
Page 718 and 719:
descriptions or descriptions of ope
Page 720 and 721:
2. SUWlARY Cost estimates for const
Page 722 and 723:
3. CONCEPT DEVELOPFIENT .3.1' .HARD
Page 724 and 725:
..: +". .. . . : ,. \,.L . . , .: f
Page 726 and 727:
., %W ; : ;,' : .? vent system cons
Page 728 and 729:
2 ft 6 in. 3 ft\ \ - N SLOPE SLOPE
Page 730 and 731:
Tank Capacity, Gal. Tank Diameter,
Page 732 and 733:
7 ft 6 in.
Page 734 and 735:
auxiliary feedwater and refueling w
Page 739:
................ ................ -
Page 748 and 749:
I .,I I , , . ............. .),.I.
Page 750:
I i , .. ! 'It-
Page 758:
LLYtL GMDL PLUS 73 it
Page 763 and 764:
and roof are of reinforced concrete
Page 766 and 767:
tection cabinets installed in the s
Page 768 and 769:
ndependent. Two ha? f-size tanks we
Page 770 and 771:
BORON INJECTION TANK No. Required T
Page 772 and 773:
Design Pressure, PSIG Design Temper
Page 774 and 775:
Doalgn Pranouto, PSIC 150 Design Te
Page 776:
. Provides for isolation of fluid l
Page 780:
I-- 38.7~1 (127 ftj Figare 3-21. U
Page 784 and 785:
I ( N.C.* I I I 4-kV CLASS 1E EMERG
Page 786 and 787:
, Alignment of reactor coolant pump
Page 788 and 789:
Electrical Power The major electric
Page 790 and 791:
The cooling air inlet and discharge
Page 792 and 793:
Design Temperature, "F Material of
Page 794 and 795:
Design Pressure, PSIS Deslqn Tcnper
Page 796 and 797:
DIESEL GENET(ATOR - LVBE OIL STORAG
Page 798 and 799:
Table 3-5 1:~:s the elping concecti
Page 800 and 801:
Loop J lC.L.1 Loop 1 lC.L.I-*:..mal
Page 802 and 803:
ability to isolate it to prevent lo
Page 804 and 805:
The excess letdown line is a small
Page 806 and 807:
4.1 GENERAL I 4. COST ESTIf4ATES Th
Page 808 and 809:
4.2.2 , Hardening Option 2, Reinfor
Page 810 and 811:
xcavat ion and Backfill Mat, 3 feet
Page 812 and 813:
TABLE 4-5 STUDY ESTIMATE, NOVEMBER
Page 814 and 815:
ITEM OF WORK TABLE 4-7 STUDY ESTIMA
Page 816 and 817:
The approach to the estimate, there
Page 818 and 819:
Substructure Excavation and Backfi
Page 820 and 821:
TABLE 4-10 STUDY ESTIMATE, NOVEMBER
Page 823 and 824:
6L:ained. In tk,e case of rne RHi+
Page 825 and 826:
TECHNICAL MPlORANDUn EVALUATION OF
Page 827 and 828:
TECHNICAL MEMORANWn ABGQNNE NATIONA
Page 829 and 830:
4.1 Sources of Information .4.2 Air
Page 831 and 832:
polar Plot for a11 hudiur hndira Ac
Page 833 and 834:
Thir report providu a revieu and ev
Page 835 and 836:
extenrively rtudied, but other crar
Page 837 and 838:
; 6 . ..,~ spective, presmt' polici
Page 839 and 840:
8 narios. mechaniraa, ad credibilit
Page 841 and 842:
ased on aircraft and topographical
Page 843 and 844:
IAU Safmty Gui& ad include the dete
Page 845 and 846:
4.1 Sources of Information 4. AIRCR
Page 847 and 848:
General Aviation refera to the oper
Page 849 and 850:
18 accounted for 81 percent of all
Page 851 and 852:
Table 1. Critical Civil Aviation Ac
Page 853:
Fig. 1 Polar Plot for all Canadian
Page 856 and 857:
2 5 procedures a d directions, misj
Page 858 and 859:
2 1 thane rerult umarired belw for
Page 860 and 861:
These race# aaruw tha: a crash can
Page 862 and 863:
hble 6 Detailed Crash btes - Fatal
Page 864 and 865:
DISTANCE FROM LANDING OR TAKE -OFF
Page 866 and 867:
the calculatiod where desirable. Bo
Page 868 and 869:
i are equivalent to randm craah eve
Page 870 and 871:
T PATH Fig. 5. Crash Sites Orthonor
Page 872 and 873:
accidents froll 1962 to 1966, 26 fi
Page 874 and 875:
Uircellaneous 0.01 mf* 0.02 mi2 tn*
Page 876 and 877:
4 5 large ones within 75 oiler. His
Page 878 and 879:
4 7 giw aircraft crashing into the
Page 880 and 881:
0 emergency core cooling system (EC
Page 882 and 883:
zero: Paat .xh?ience h a ahown that
Page 884 and 885:
5 3 lw it to deprearurirs the PHtS
Page 886 and 887:
mgklw imposed upon the plant struct
Page 888 and 889:
the calculatioru were repeated with
Page 890:
strength). The reaction load for th
Page 894 and 895:
Fig. 12 Displacements-Time-~Iiutori
Page 896 and 897:
cross-sectional area of the strikin
Page 898 and 899:
LOADING AREA REINPORCEYE STILL E'LA
Page 900 and 901:
4 6 lo-' 2 4 6 10 t? 2j3 PERIOD t s
Page 902 and 903:
Fig. 18 Comparinon of Response spec
Page 904 and 905:
I Fig. 22 Response Spectra. Compari
Page 906 and 907:
the gener.~?vicinity of the crash s
Page 908 and 909:
77 such an even nvironaent will be
Page 910 and 911:
, .';,,>,~robabilit~ . . . _ of occ
Page 912 and 913:
and conclurio 81 0 1 Aviation aircr
Page 914 and 915:
itself a coditional probability, co
Page 916 and 917:
acceptrblY -11, and the risk evalua
Page 918:
then aviation zones concentrate tra
Page 921 and 922:
Scenarios - Plan: methodologies for
Page 923 and 924:
REFERENCES 1. U.S. Nuclear Regulato
Page 925 and 926:
Crarrro, U. and Lucenet, C., "Zvalu
Page 927 and 928:
96 Viti, C., Olivieri, X., and Trav
Page 929 and 930:
Offslte Hazards: Aircraft Crash Typ
Page 931 and 932:
Offaite Hazards: Aircraft Crash Spe
Page 933 and 934:
so11.1tion of the dynamic analysic
Page 935 and 936:
I 104 airport. Inpact forciw functi
Page 937 and 938:
Offaite Hazards: Aircraft Crash Typ
Page 939 and 940:
Offsite rcraft Crash diagram and co
Page 941 and 942:
hi tr a numbar of techniques which
Page 943 and 944:
aircraft fraac is examined and it w
Page 945 and 946:
113 idual probabilities that an air
Page 947 and 948:
'Ihir paper giver a rrm~ry of extre
Page 949 and 950:
111 Offrite Rarardr craft Crash -pa
Page 951 and 952:
Internal: E. S. Beckjord C. E. Till
Page 953 and 954:
ABSTRACT The purpose of this projec
Page 955 and 956:
, . 5.0 HUMAN RELIABILITY ANALYSIS
Page 957 and 958:
Given an carthquakc large enough to
Page 959 and 960:
Relay chatter was not treated at al
Page 961 and 962:
6.1 lntroductlon SECTION 6 SUhlhlAR
Page 963 and 964:
were found to be important). These
Page 965 and 966:
6.3 Plant-spccllic lnslghts for LaS
Page 967 and 968:
11) We believe that, on balance, th
Page 969 and 970:
conservative but we are not certain
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SUBJECT: COMMENTS ON NRC PROPOSED RULE ...

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